Text

Amends 98 & 85 to Licenses DPR-58 & DPR-74,respectively, Revising Tech Specs by Removing Duplicative Inservice Insp & Inservice Testing Requirements
	ML17324B007
Person / Time
Site:	Cook
Issue date:	07/29/1986
From:	Youngblood B; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17324B008	List: ML17324B007; ML17324B009;
References
	NUDOCS 8608080154
	Download: ML17324B007 (37)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD'. COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No.

DPR-58 1.

The Nuclear Regulatory CoIImission (the Commission) has found that:

A.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated May 10, 1983 as supplemented by letter dated June 20, 1986, complies with the standards and re-quirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Cotanission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.

DPR-58 is hereby amended to read as follows:

Bbosoaol " 050003i5

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PDR ADOCY PDR p

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A 3.

4.

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 98

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

The change in Technical Specifications is to become effective within 90 days of issuance of the amendment.

In the period b'etween,issuance of the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems, components, or operation existing at the'ime.

The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alternative.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 29, 1986

/

B. J.

Youngblood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A, NRR PWR¹4:DPWR-A DWigginton:mac 06/+/86 PWRg4 DPWR-A t85h n

06/07

/86 OEL ~ g PWR¹4:DPWR-A B Youngblood (Jf/ ~( /86 0 / [(,/86

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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.

98 FACILITY OPERATING LICENSE NO.

DPR-58 AMENDMENT NO.

85 FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET NOS. 50-315 AND 50-316 Revise Appendix A as follows:

Remove Pa es Insert Pa es Untt 1

3/4 0-2 3/4 1-11 3/4 1-12 3/4 4-7 3/4 4-8 3/4 4-9 3/4 4-10 3/4 4-11 3/4 4-12 3/4 4-33 3/4 4-34 3/4 4-35 3/4 4-36 3/4 4-37 3/4 4-38 3/4 4-39 3/4 4-40 3/4 4-41 thru 48 3/4 5-4 3/4 5-5 3/4 5-6 3/4 6-10 3/4 6-11 3/4 7-15 3/4 7-16.

3/4 7-17 3/4 7-18 B 3/4 4-12 3/4 6-12*

3/4 5-6a Untt 2 3/4 1-11

No change.

Included for convenience only.

Unit 1

3/4 0-2 3/4 l-ll 3/4 1-12 3/4 4-7 3/4 4-8 3/4 4-9 3/4 4-10 3/4 4-11 3/4.4-12 3/4 4-33 3/4 4-34 3/4 4-35 3/4 4-36 3/4 4-37 3/4 4-38 3/4 4-39 3/4 4-40 3/4 5-4 3/4 5-5 3/4 5-6 3/4 6-10 3/4 6-11 3/4 7-15 3/4 7-16 3/4 7-17 3/4 7-18 B 3/4 4-12 3/4 6-12*

B3/4 0-5 Untt 2 3/4 1-11

SORV 4,0,1 Surveillance requirements shall be applicable during the OPERATIONAL MODES or other conditions specified f'r individual Limiting Conditians for Oper ation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed vithin the specified time interval with:

a.

A maximum allovable extension not to exceed 255 of the surveillance interval, and b.

A total maximum combined time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

4.0.3 Performance of a Surveillance Requirement vithin the specified time interval shall constitute campliancc vith OPERABILITY requirements f'r a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

Surveillance requirements do not have to be performed on inoper able equipment.

4.0.4 Entry inta an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requiremen (s) associated w'h :he Limitirg Condition for Operation have been per f'ormed within the stated surveillance interval or as othervise specified.

4.0.5 Surveillance Requirements for 'rscrv'ce inspect'on and testing of ASKS Code C'ss ly 2, and 3 components shall be applicable as follows:

a ~

Inservice inspection of ASME Code Class 1, 2, and 3 componcrts ard irservice testing of'SHE Code C'ass 1,

2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),

except where spec'fic written relief has been granted by the Commission pursuant ta 10 CFR 50, Section 50,55a(g) (6) (i).

D. C.

COCK - UNIT I 3/4 0-2 pgnendmcnt No ~ 98

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REACTIVE.

CONTROL SYST2<5 CHARGING PUMPS - OPERArNG LIMITING CONOITION FOR OPERATION

3. 1.2.4 At least ~o charging pumps shall be OPHASLE.

APPLICABILITY:

HOOES I, 2, 3 and 4.

ACTION:

Nth only one charging pump OPHAGLE, restore at least ~ charging pumps to OPERASLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANOBY ~i Win the nex.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least t~o charging pumps to OPUASLE status

~'.'thin the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLO SHUTDOWN within the l'ollcwing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

5'JRVEILUNC="REOUIR&ENi5 4.1.2.4 At least two charging pumps shall be demonstrated OPERABLE by verifying, that on recirculation flow, each pump develops a discharge pressure of) 2405

!psig when tested pursuant to Specification 4.0.5 at least once per 31 days on a STAGGERED TEST BASIS.

D. C.

COOK - UNIT 1 3/4 1-12 Amendment No.

98

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REACTOR COOLANT SYSTEM SURVEILLANCE RE UIRE2fENTS (Continued )

I.

All nonplugged tubes that previously had detectable vali penecrations

+20Z).

2.

Tubes in those areas where experience has indicated potential problems.

3.

A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall be performed on each se1ected tube.

If any selected tube does not permit the passage of the eddy currenc probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c.

The cubes selecced as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected co a part'al tube inspection provided:

2.

The tubes selecced for these samples include the cubes from those areas of the tube sheet array vhere cubes vith imperfections were previously found.

The inspecc'ons include those portions of the tubes where imperfections vere previously found.

The resulcs of each sample inspection shall be classified into one of che fol.loving chree categories.

Catenal..v Ins ec cion Results C-I Less Chan SZ of the total cubes inspected are degraded tubes and none of the 'inspected tubes are defective.

One or more cubes, buc not more chan IX of

@he total tubes inspected are defective, or between 5X and 10X of the total tubes inspected are degraded cubes.

C-3.

More than 10X of c5e total tubes inspected are degraded tubes or more than IZ of the inspected tubes are defeccive.

Note:

ln all inspections, previously degraded tubes must exhibit significant ()IOZ) further vali penetrations to be included in the above percentage calculations.

D. C.

COOK - UNIT 1 3/4 4-8 Amendment No.

98

REACTOR COOLANi SYSTEM SURVEILLANCE REQUIREMENTS (Ccntinued'i 4..4.5.3 Inspection Frequencies

- The above required inservice inspections of steam generator tuoes shall be per.ormed at the following frequencies:

The first inservice inspection sha11 be performed after 5

fffe tive Full Power Months but within 24 calendar months of initial criticaiity.

Subsequent inservic inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.

I two consecu-tive inspections f'ollowing service under AVT conditions, not including the pr eservice inspec-ion, result in all inspection tissu)ts falling into the C-1 cateaory or if two consecutive inspe tions demonstrate that previously observed degradation has no-continued and no additional degradation has occur'red, the inspection interval may be extended to a maximum of once per 40 months.

Lf the results of the inservico inspection of a s-an generator conducted in accordance with Table 4.4 2 at 40 month intervals.all in Cateaory C-3, the inspection frequency shall be increased to a. least cnc per 20 months.

The increase in inspec:ion freauency shall aooly until the subseauent inspections satis, y :he cri:eria o, Soeci ica ion 4.4..3.a;

he inte. val may then be exterded to a maximum o-onc per 4" months.

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Additional, unscheduled inservic inspec-ions shall be performed On each steam generator in accordance with the rirst samoie fnspec:ion specified in Table 4.4-2 during the shut"own su"sequer.:

to any of the following conditions:

1.

Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sne t welds) in excess of the limits of Speci ication 3.4.6.2.

2.

A seismic occurrmce greater than the Operating Basis Earthquake.

3.

A loss-of-coolant accident requiring ac.uation of.he engine red safeguar."s.

4, A main s

earn line or feedwater line break.

D ~ C ~

COOK UNIT I

3/4 4-9 Amendment No.

98

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS Continued 4.4.5.4 Acce tance Criteria a.

As used in this Specification:

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1 bb' th dl 1,11th or contour of a tube from that required by fabrication drawings or specifications.

Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.

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tg wear or general corrosion occurring on either inside or outside of a tube.

3.

Oearaded Tube means a tube containing imper ec.ions

>20" n

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Oe radation-means the percentage of the tube wall tnlc ness arfected or removed by degradation.

5.

Oefect smans an imperfection ef such severity that it exceeds the plugging limit.

A tube containing a defect is defective.

6.

Plugging L'.'mit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior Co the next inspection and is equal to 40" of the nominal Cube wall thickness.

7.

Unserviceable describes the condition of a Cube if it T

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structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.

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tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold lea.

D. C.

COOK UNET 1 3/4 4-10 Amendment No.

98

REACTOR COOLANT SY~i SURYETLLWCE REOUIRE<~i (Conti nued )

The szaa generat"r sha11 be deterefned OPGNLE after campl etang the corresponding actfons (plug a11 tubes exceedfng t& pluggfnq I fant and aII tubes containing through-wall cracks) required by Table 4.4-Z.

ci Follcwfnq each inservice inspection of stela generator

tubes, the number a

tubes plugged in ee>

s eaa generator shoal.I.

be repcrted w Ne Cenaissfcn wi >in 15 days.

Tao amplete results

o. the stew~

generator

<be fnservfce

$ nspectfon shall be included in the Annuel Oper@ting Report far the perfcd in which thfs irwpectfcn was aunpleted.

Thfs report shall include:

1.

Neer and extent af ~es inspected.

Z. ~ fcn wd pe~nt c. well-Nickress penetratfcn fcr each ir.c'cn.. 'm 'mgerrectiar..

3.

identification cf tubes plugged.

Pesul w of steam generator ube inspect-'cns which

@II inta Category C-3 and eqvfr pramat nctfffc tfcn of tNe Cciih ssfcn shail be reported'".ursuent

"" Spec'.f-c ticn 6.9.1 prior ta r esumpt'on of pl nt operation.

The wr ftten fcllcwup af this report shall provide a description cf investige-icns conducted ta determine cause o-the nbe degr~ 'etfar. enc c"rrective me~sures aken a prevent r

ur. enc O.C.

COOK - UNIT l 3/4 4-11 Amendment No. 98

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C)OO PC I

TABI.E 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BF.

INSPECTED DURING INSERVICE INSPECTION Preservfce Inspection Yea No. of Steam Generators per Unit Four First Inservice Inspection Second 6 Subsequent Inservice Inspections Two One.2 e

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Table Notation; The inservice inspection may be limited tr one steam generator on a rotating schedule encompassing 3

N X of the tubes (where N Js the number of steam generators in the plant) if the results of the first or previous inspectior i indicate that all steam generators are performing in a like manner, Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam generators, Under such circumstances the sample sequence shall be modified to inspect the most severe conditions, 2.

Each of the other two steam generators not inspected during the first inservice inspection shall be inspected during the second and third inspections, The fourth and subsequent in'spections shall follow the instructions described in I above,-

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REACTOR COOLAN SYSTEM This page intentionally left blank.

D.

C.

COOK - UNIT 1 3/4 4-34 Amendment No.

REACTOR CCOL'NT SYST"-9 RELIEF VALVES " OPERATING LIMITING CONDIT ON FOR OP(RATION 3.4.11 Three power operated relief valves (PORYs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

C.

fifth one or more PORY(s) inoperable, wi-Nfn 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE situs or close the associated block valve(s) and remove power from the block valve(s); otherwise, be in at leas HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SriUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Wf ~5 one or c'.ore block valve(s) inoperable, wi-.hin 'our ei<<her (1) restore the block valve(s) to OPERABLE status, or (2) close the block valve(s) and remove oower from the block valve(s), or (3) close the associated PGRV(s) and remove power from the associated solenoid valve(s); otherwise, e in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTOOW w.'thin the fol',owing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ."

Ine provisions o

Speci;ication 3.0.>> are not applic&~le.

CURVE LLAHCE RE"UIR~>EN 5

4.4.%.1 Bach of the thr e PORVs shall be demonstrated OP%BABLE:

At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding vaive operation, and b.

At 'feast once per 18 months by performance of a CHANNEL CALIBRATION.

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%hen ACTION 3.$.1'.b. (3) is aoplied, no repor-pursuant to Soeci ication 6.9.1.9 is required;or the PORV.

D. C.

COOK UNIT 1 3/4 4-35 Amendment No.

REACTOR COOLANT SYSTEM SVRVEILDNCE REOVIREHEHTS Continued) 4.4.I1.2 Each of the three block valves shall be demonstrated OPERABLE at least once per 92 days by operating

.he valve through one complete cycle of j full travel.

The block valve(s) do not have to be tested nor is a report

'required pursuant to Specification 6.9.1.9 when ACTION 3.4.ll.a is applied.

4.4.21.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per M months by operating the valves through a complete cycle of full travel while the emergency buses are energized by the onsite diesel generators and onsite plant batteries.

This testing can be performed in conjunction with the requirements of Specifications 4.8. 1.1.2.b and 4.8.2.3.2.c.

D. C.

COOK - UNIT 1 3/4 4-36 Amendment No.

98

. XXPX$Ã IW'OIDZTIO 8 lOR OPE TXOS 3.4.12.1 it least one of the keactor Vessel head vent paths, conai,sting of t<<o r~tely operated valves in aeriea, pevetad froa Class lk DC

bnasea, shall be CFK1ASLZ and cleaed.

WAAFS I, 2, 3, aad 4o a ~

Pith both ot the Re~tot Vessel head veat paths iaoperable, aad at IeasC one of Che Preaauriaat atea%

apace vent paths 0?SXQLk (aee Specification 3.4.12.2), operation in MODES 1, 2, 3 ot 4 aay coaC 11Lue y pfovided Che Blepetab le vent paChs are na IRCa BLed c lclaed

<<ith pover rmved froa the valve actnaters of all the rwtelf operated valves in all of the inoperable vent paths; restore at least one of the Rector Vessel head vent paths vithh 30 days ot be in NT STAÃDbT vithia 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months aad ia COLD SRUTM8 vithia the folloviag 30 boors

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arith both of the keacter Vessel head vent paths aad both of the Pteaauriter ateaa apace vent paths Inoperable; aaIntain the inoperable vent paths closed vith po<<er reeved froa the valve actuatora of all of the reately operated valves in all of the iaoyerable vent paths; restere oae of the iaoperable vent paths fraa either the Reactor Vessel head vent or the Preaauriaer ataaa apace <<ithia 72 hears or be in ROT STAIDST vithIn 6 heats aad ia COLD SATYR vithia the folio<<by 30 hears.

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The prevision of Specification 3.0.4 are aot applicable.

D. C.

COOK - UNIT 1 3/4 4"37 Amendment No.

4 ~ 4 ~ 'J2,$

Both Reactor Vessel head vent paths shall be deaeastrated OPERABLE at least once yer 18 months by:

Verifying the ccanen manual isolation valve ia the Reeetec vessel

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head vent is sealed in Che open position g.

Cycling each of the cenotely opecated valves 1a each path through at least oae complete cycle of full travel from the Control Rooa while ia Bodes 5 or 6.

Verifying tier through boCh ot the Reactor Vessel head vent yaths during veating operation,

@hi,le ia Hodes 5 or 6.

Surveillance roquiraseats to deaonstrate the operability ot each Reactor Vessel head vent yath @111 be performed the next time the unit enters HCDES 5 oc' tolloviag the issuance of this Technical Speeifieatioa, aad aftec the apyroyciate Plant procedures have been written.

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COOK QMIT 1 3/4 4-38 Aagnchaent ceo 98

OR COO 0

3.4.12.2 kt least one of the Pressurizer steaa space vent paths, each consisting of tvo reaotely operatel valves in series, povered fina Class IE X busses, shall be ORRIS'ad closed.

emsS 1, 2, 3 ~ and 4.

kE2E:

Vith both of the Pressurizer steaa space vent paths iuoperible, and at least one of the Reactor Vessel head veat paths OPERAS'see Specificatioa 3.4.12.1),

operation iu IDES 1 ~ 2, 3 or 4 may

continue, provided the inoperable vent paths are aamtaiaed chsed vith the pover rmved froa the valve actuators of all the remotely operated valves in all of the inoperable vent paths, restore at least one of the Pressurizer stoma space veat paths vithin 30 days or be ia ROT KNDST vithh 6 Pours and in COLD SEUTDAAl ia the folloving 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

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Vith both of the Pressurizer steaa space vent paths aud both of the Reactor Vessel heal vent paths inoperable; aaiutam the inoperable vent paths closed vith pomr reneved froa the valve actuators of all of the reaetely operated valves in all of the inoperable veat paths; restore oue of the iaoperable vent paths froa either the Reactor Vessel head vent or the Pressurizer steca space vithin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in IRT STLHDST vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months aud ia COLD SELDOMÃ vithia the folloviug 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

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The provisions of Specificatioa 3.0.4 are uot applicable.

D. C.

COOK - UNIT 1 3/4 4-39 Amendment No.

98

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4.4.$ 2.2 Both ~surfer steaa space vent paths shall be demnnstrated OMLLBLE at least once yer 18 months by:

t.

Verifying the ccamn manual isolation valve ia the Pressurizer steam space vent Ls sealed in the open yositioa.

2.

Cycling each of the refcotely operated valves Sn each path through at least one complete cycle of full travel froa the Control Rooa shee in Nodes 5 oc 6.

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Verifying flaw tough both of the Pressurizer steaa space vent yaths during venting opec atioa, while in Modes 5 or 6

~eillance requirements to demonstrate the operability of each Pressurizer steam space veat path will be performed the next time the uait eaters NODES 5 oc' follcnring the issuance of this Technical Specificatioa, and aftec the appropriate Plant procedures have been e'ittee.

3/4 4-40 Aeendaant ceo.98

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EMERGENCY CORE COOLI."lG SYST=RS SURVEILLANCE REOUIRB)ENTS (Continued) d.

At least once per 18 months by:

e.

l.

Ver ifying automatic isolation and interlock action of the RHR systan from the Reactor Coolant System when the Reactor Coolant Systen pressure is above 600 psig.

2.

A visual inspection of the conta rment sump and verifying that the subsystan suction inlets are not restricted by debris and that the sump components (trash racks, sere ns, etc.)

show no evidence of structural distress or abnormal corrosion.

At least once per 18 months, during shutdown, by':

1.

Verifying that each automatic valve in the low path actuates to its corre t position on a Safety Injection test signal.

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a)

Centrifugal charging pump b)

Safety injection pump c)

Residual hea.

removal pump By verifying that each of the,ollowing pumps develoos the indicated discharge pressure on re irculation low wnen tested pursuant to Specification 4.0.5 at >east once per

~1 da~s on a STAGGERED TEST BASIS.

1.

Centrifugal charging pump

> 2405 psig 1445 psig 195 psig 2.

Safety Injection pump 3.

Residual heat removal pump Hy verifyino the correct position of e.ch mechanical stop for'he following Emergency Core Cooling System throttle valves:

Within 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s following completion of each valve stroking operation or maintenance on the valve when the ECCS sub-systans are required to be OPERABLE.

2.

Verifying that each of the following pumps start automatically upon receipt of a safety inje" ion tes signal:

0.

C.

COOK - UNIT 1 3/4 5-5 Amendment No.

98

,6/

RGEHCY CORE COOLIHG SY MS SURVEELi>NCE REOI'IREHEHTS (Continued) 2.

At least once per 18 months.

Boron Injection Thr ottl e Valves Valve Number Safety Injection Throttle Valves Valve Number

1. f -SI-141 L1 2.

t.-SI-141 L2 3.

I

-SI-141 L3 4.

1

-SI-141 L4.

L t

SI 121 H

2. t

-SI-121 S

h.

By performing a flow balance test during shu.dcwn following completion of modifications to the ECCS subsystem that alter th subsystem flow chara teri sti cs and veri fying the following flow rates:

~

. I Boron Injection System Sinale Pumr~

Loop 1 Bo~on Injection flow 117.5 apm 4.oop 2 Boron Injection flow 117.5 gpm Loop 3 Boron Injection Flow 117.5 gpm Loop 4 Boron Injection Flow 117.5 apm Safety Injection System Sinale'umo""

Loop 1 and 4 Cold Leg Flow > 300 gpm Coop 2 and 3 Cold Leg Flow > 300 gpm "The flow r ate in each Boron Inie.ion (BI) line should be adjusted to provide 117. 5 gpm (nominal) 'low into each loop.

Vnder these conditions there is zero mini-flow and 80 cpm simulated RCP seal injection line flow.

The ac-ual flow in each BI line may deviate from the nominal so long as the difference between the highest and lowest low is 10 apm or less and the to:al flow o

the four branch lines does not exceed 470 gpm.

Hinimum flow (total flow) required is 345.8 gpm to the thr e most conservative (lowest flow) branch lines.

'Combined Loop I, 2, 3, and 4 Cold Leg Flow (single pump) less than or equal to 640 gpm.

Total SIS (single pump) flow, including miniflow shall not exceed 700 gpm.

I 0.

C.

COOK - UNIT 1

3/4 5"6 Amendment No.

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CONTAINMENT SYSTEM SPRAY ADDITIVE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 The spray additive system shall be OPERABLE with:

a.

A spray additive tank containing at least 4000 gallons of not less than 30 percent by weight NaOH solution, and b.

Two spray additive eductors each capable of adding NaOH solu-tion from the chemical additive tank to a containment spray system pump flow.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the spray additive system inoperable, restore the system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6

hours; restore the soray additive system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.2.2 The spray additive system shall be demonstrated OPERABLE:

At least once per 31 days by:

2.

Cycling each testable power operated or automatic valve in the flow path through at least one complete cycle of full travel.

I Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.'.

At least once per 6 months by:

l.

Verifying the solution level in the tank, and 2.

Verifying the concentration of the NaOH solution by chemical analysis.

D. C.

COOK-UNIT 1

3/4 6-12 Amendment No. 98

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D. C.

COOK UNIT 1 3/4 7-16 Amendment No.

98

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C.

COOK - UNIT 1

3/4 7-18 amendment No. 98

APPLICABILITY BASES 4,0.5 This specif'cation ensures that iaservice inspection of ASME Code Class 1,

2 and 3 components and inservice cesting of ASME Code Class 1,

2 and 3 pumps and valves will be performed in accordance with a periodically updated,'version of Section XI of the ASME Boilex'ad Pressure Vessel Code and Addenda as requix'ed by 10 CFR 50.55a.

Rel'ef from any of the above requirements has been provided in writing by the Commission and is not a part of these technical specifications.

This spec'fication includes a clarification of the frequencies for performing che inservice inspect'on and testing accivicies required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

This clarificatioa is provided co ensure consistency in surveillance intervals throughout these techaical specifications and to remove any ambiguities relative to the frequencies for performing and the required inservice inspection and testing activities.

Undex'he terms of this specification, the more rescriccive requiremeacs of the Technical Specifications take precedence over che ASME Boilez and Pressure Vessel Code and applicable Addenda.

Foz

example, the requirements of Specification 4.0.4 to perform surveillance activities pr'or to eatry into an OPERATIONAL MODE or other specif'ed applicability coadicion takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to one week after return to normal operacion.

And for

example, the TechnicalSpecification defiaition of OPERABLE does not grant a grace period befox'e a device that is not capable of performing its specified function is declared inoperable and takes pzeceoence over che ASME Boiler and Pressure Vessel Code provision which allows a valve co be 'ncapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

D ~ C.

COOK - UNIT 1

B 3/4 0>>5 Amendment No.

98

REACTOR COOLANT SYSTEM 3/4.4. 10 STRUCTURAL INTEGRITY The inspection and testing programs for ASME Code Class 1,

2 aad 3 components ensure that the structural integrity of these compoaeats will be maintaiaed at an acceptable level throughout the life of the plant

~

To the extent applicable, the iaspection program for these components is in compliance vith Section XI of the ASME Boiler and Pressure Vessel Code.

D.

C ~

COOK UNIT 1

B 3/4 4-12 Amendment No.

98

3.1.2.3 One charging pump in the boron in]ection flow path required by Specification 3.1.2.1 shall be OPG46LE and capable of being powered from an OPERPJP ~ emergency bus.

KODES 5 an'd 6, BKl~&<

a.

With no charging pump QPEPMLK, suspend all operations invol'v'ng CORK ALTERATIONS or positive reactivity changes.

b.

With more than one charging pump OPHLABLK or with a safety in]ection pump(s)

OPERABLE when the temperature of any RCS cold leg is less than or equal to 152 F, unless the reactor vessel head is removed, zemove the additional chazging pump(s) and the safety in]ection pump(s) motor circuit breakers from the electrical power circuit within one hour.

C.

The provisions of Specification 3.0.3 ar not applicable.

4.1.2.3.1 The above required charging pump shall be demonstrated OPERASLK by verifying, that on zecirculation flow, the pump develops a discharge pressure of p 239O psig when tested pursuant to Specification 4.0.5.

P 4.1.2.3.2 All charg'ng pumps and safety in)ection pumps, excluding the above required OPERABLE charging pump, shall be. demonstrated inoperable by v'erifying that the motor circuit breakers have been removed from their electrical power supply c'zcuits at least once per'2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ,. except when:

a.

The reactor vessel head is removed, or b.

The temperatuze of all RCS cold legs is greater than 152 F.

For purposes of this specification, addition of water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.

D.

C.

COOK - UNIT 2 3/4 1-11 AMENDMENT NO.

~p,R Rfey

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UNITED STATES NUTBAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.85 License No.

DPR-74 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated May 10, 1983 as supplemented by letter dated June 20, 1986, complies with the standards and re-quirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.

DPR-74 is hereby amended to read as follows:

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85

, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The change in Technical Specifications is to become effective within 90 days of issuance of the amendment.

In the 'period between issuance of the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical, Specifications for the systems, components, or operation existing at the time.

The period of time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alternative.

4.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 29, 1986 B. J.

Youngblood, Director PWR Project Directorate P4 Division of PWR Licensing-A, NRR PWR84:DPWR-A DWigg'nton:mac 06/p /86 P IR 4:

PWR-A 06/g$ /86 OELD~~

PWR64:DPWR-A B'JYoungblood OP/ ~ /86 0$/gp/86

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